Abstract

The particulars of the design of new-generation ASCTP and experience in implementing the system in the No. 3 unit of the Kalininskaya nuclear power plant are examined. The basic requirements and the main approaches for developing ASCTP for the power-generating units of nuclear power plants with newgeneration VVER, including protection from failures for general reasons in the safety control systems, expansion of the functions of the system of the top block level, intellectually signaling, automation level of technological processes, and servicing of the means of automation are presented. It is noted that the principle of optimizing the application of modern information technologies taking account of experience in design and operation of power-generating units with mandatory maintenance of the updated base must play an important role in determining the requirements for and making technical decisions concerning ASCTP for new-generation VVER.

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